Method for filtration of gas effluents from an industrial installation

ABSTRACT

A membrane for a method for filtration of gas effluents from an industrial installation including a wall having an internal surface and an external surface, the wall having pores of variable dimensions in the radial direction and in the longitudinal direction of the wall.

CROSS REFERENCE TO RELATED APPLICATIONS

This application is claiming priority based on French Patent ApplicationNo. 1200076 filed Jan. 10, 2012 and U.S. Provisional Patent ApplicationNo. 61/659,693 filed Jun. 14, 2012, the contents of all of which areincorporated herein by reference in their entirety.

The present invention relates to a membrane for a method for filteringgas effluents on industrial installations, and notably in the field ofproduction of energy of nuclear origin.

More particularly, the invention may allow selective sorting at a highflow rate of chemical and/or radioactive species in the gas state,notably by membrane separation, the goal mainly being the securedrecovery of gas discharges produced on the installation under normaloperating and abnormal operating situations, in particular during aserious accident.

In the particular case of a nuclear installation, the impact on theenvironment is mainly related to the radioactive, thermal and chemicalcharacteristics of the waste. Depending on their level of radioactivityand on their chemical composition, the radioactive elements are stored,processed and then packaged in order to form waste. Some of theseradioactive elements are discharged in gaseous form into the atmosphere,of course at concentrations strictly defined by the applicableregulations. The gas discharges produced during normal operationgenerally stem from the purification and filtration circuits of thepower plant, which collect a portion of the radioactive elementsgenerated by the operation of the systems and equipment making up theinstallation. For example in France, these radioactive gas dischargesproduced by nuclear power plants may typically represent of the order of1.1% of the allowed limit for rare or noble gases, 11.1% for tritium and3.6% for iodines (both organic and inorganic). Helium, neon, argon,krypton, xenon and radon form the family of rare gases, group zero ofthe Periodic Table of the Chemical Elements, but the name of noble gaseswill be used hereafter as it is recommended by the IUPAC (InternationalUnion of Pure and Applied Chemistry) and by the “Bulletin Officiel duMinistère Français de I'Éducation nationale”. These wastes areordinarily of low activity and the radionuclides which they contain arenot very toxic and generally have a short period. It should be notedthat gas discharges contain solid and liquid particles. Those having aradioactive nature form aerosols with a highly variable grain size.Fission phenomena encountered on suspended dusts produce radionuclidessuch as halogens, noble gases, tritium and carbon 14. The compositionand the radioactivity of the thereby formed aerosols depend to a greatextent on the type of reactor and on the emission routes.

Ordinarily, the gas effluents of a nuclear power plant are treatedbefore they are discharged into the atmosphere in order to extract mostradioactive elements. The current practice consists of filtering thecontaminated gases and the ventilation air of the premises so as toextract the radioactive particles therefrom before their discharge intothe atmosphere. The air ventilation and purification systems generallyinclude coarse pre-filters associated with absolute filters. As anindication, it will be noted that for particles with a diameter of theorder of 0.3 mm, the extraction yield normally attains at least 99.9%.

Radioactive iodine is extracted by means of filters with impregnatedcharcoal, associated with dust filters. Impregnation of the coal isrequired in order to retain the iodinated organic compounds.

Radioactive noble gases which evolve from the fuel elements are releasedinto the atmosphere in a deferred mode after disintegration in order toreduce the level of activity. Two methods are used for this purpose:buffer storage in special reservoirs or passage through several layersof charcoal. For storage, the noble gases and the carrier gas aretherefore introduced by pumping them into sealed reservoirs where theyare kept until their release is authorized into the atmosphere. Theother method consists of having the effluent pass into a series ofcharcoal columns which delay the progress of the noble gases relativelyto the carrier gases, thereby facilitating their radioactive decay.

Most methods for processing and packaging waste of low and mediumactivity are now well developed and are used on an industrial scale. Thetechnology is sufficiently advanced for ensuring efficient management ofthe waste from the power plants, but improvements are always possibleand desirable. The increasing budget for this management encourages theadoption of methods and techniques with which the produced amounts maybe reduced to a minimum and the study of new means for further reducingthe volumes at the processing and packaging stage. As an example, let usmention the use of specific mineral sorbents for improving processing ofliquid waste; the membrane technique, also for treating liquid waste;the drying of resins in beads and of muds from filters; the incinerationof depleted ion exchange resins; dry cleaning of clothes and otherprotective textile materials for reducing the volume of laundry waters;the use of highly resistant hermetically sealed containers for packagingdried filter muds; vitrification of certain wastes of medium activityfor reducing the volumes to be removed; and overcompaction of non-fuelwaste.

These techniques corresponding to the recent industrial state of the artwill perhaps not be all universally applied to the management of waste,in particular at nuclear power plants, but this research and developmenteffort shows the great care which the nuclear industry and power plantoperators bring to the safety and to the economy of waste management,and announces enhancements.

The invention relates to the use in a specific method of a membranetechnique to be used for processing gas effluents generated byindustrial and notably nuclear installations.

In the case of a serious accident on the reactor of a nuclear powerplant using the water reactor technology, i.e. about 95% of the presentworldwide installed base, the atmosphere inside the reactor buildingchanges over time and forms a mixture containing: air, steam,uncondensable gases (essentially H₂, CO, CO₂, fission products asaerosols, vapors and gases . . . ), the proportions of which may bevariable both from a spatial and a time point of view. The increase inpressure which results from this and/or the accumulation of harmfulproducts contained in this mixture finally lead to releases into theouter environment in order to avoid a loss of mechanical integrityconsecutive to a hydrogen explosion or to the pressure exceeding the oneadmissible by the building. The fluid which escapes from the buildingmay be air, radioactive gases, steam or a mixture of fluids. An objectof this method is to separate during the degassing phase the radioactiveand/or environmentally dangerous elements as regard discharges, torecover them for an optional particular treatment for storage or forreprocessing them with view to their possible re-use and to avoid adangerous discharge into the environment.

In the early 80s, simple means were set into place on several nuclearpower plants in order to limit the consequences of accidents. One of thegoals was to be able to control and filter the gas discharges by meansof a specific system.

Presently, these so-called <<palliative>> systems are used for causing apressure drop in the reactor building by discharging the gases through afiltration process. Two different technologies exist on the operatingworldwide nuclear installed base:

-   -   a sand filtration system on which the radioactive gases are        trapped without any distinction: in the case of a serious        accident, the pressure inside the containment vessel of the        reactor building may increase more or less rapidly. By starting        the sand filtration system, it is possible to discharge in a        controlled way a portion of the gas-steam mixture. This would        avoid excessive pressurization of the containment vessel while        considerably limiting the radioactive discharges. These sand        filters mainly used in France, allow about 50% of the harmful        elements contained in the gas flow to be filtered, to be        retained but are inoperative on noble gases. FIG. 1 illustrates        a power plant 10 equipped with a sand filter 20 and a unit for        measuring waste 25 positioned upstream from the gas discharge        chimney 15;    -   a degassing system by sparging which does not allow selective        degassing. In these circuits, a portion of the water circulating        in the circuit escapes into the atmosphere as steam, notably        when it passes into the air-cooling towers, and another portion        is sent back into the environment in order to limit a too high        concentration of non-vaporizable products. This system, notably        used in Germany and in Sweden allows retention of about 75% of        the harmful elements contained in the gas flow to be filtered,        but is also inoperative on noble gases. It is very bulky (>100        m³) and difficult and therefore costly to apply and to maintain.

Both of these systems are set into operation by voluntary eithermanually or assisted action for opening sectional valves. They require adriving pressure upstream in order to generate a flow and obtainefficient filtration. Their operation is passive up to a pressurethreshold determined by the dimensioning of the filtration system andnotably by its hydraulic resistance. Below this pressure threshold,actuators and therefore an electric power supply are required forextending the filtration function. Moreover, the monitoring of variousparameters, notably environmental parameters, also requires a provisionof electric energy.

The object of the present invention is to provide a method forfiltration of contaminated and/or harmful, notably radioactive, gaseffluents, which does not reproduce the aforementioned drawbacks.

The object of the present invention is notably to provide such afiltration method which is much more efficient, allowing substantialfiltration of the totality of the harmful elements contained in the gaseffluents to be processed.

The object of the present invention is notably to provide a method whichallows both selective separation of radioactive gases during degassing,their trapping, their discrimination, their temporary storage, theiroptional processing for subsequent re-use, controlled dilution andtreatment of the contaminated atmosphere of the containment vessel of anuclear power plant.

The object of the present invention is also to provide a method forfiltering gas effluents from a nuclear power plant, with permanentavailability and able to operate continuously or intermittentlydepending on requirements.

The object of the present invention is also to provide a method forfiltering gas effluents from a nuclear power plant, which operates inthe case of a serious accident.

The object of the present invention is also to provide a device forfiltering gas effluents from an industrial installation, said deviceincluding an improved membrane.

The object of the present invention is therefore a membrane for a methodfor filtering harmful gas effluents from a industrial installation,comprising a wall including an internal surface and an external surface,said wall having pores of variable dimensions in the radial directionand in the longitudinal direction of said wall.

Advantageously, said wall is cylindrical.

Alternatively, said wall is planar.

Advantageously, said gas effluent to be processed flows longitudinallyoutside said external surface.

Advantageously, the size of the pores increases from said externalsurface to said internal surface.

Advantageously, the size of the pores increases in the longitudinaldirection of said wall.

According to a first alternative, said gas effluent to be processedconsists of the fumes of an industrial installation after an accident.

According to another alternative, said gas effluent to be processedconsists of the fumes of an industrial installation during operation.

According to another alternative, said gas effluent to be processed isextracted from a ventilation system.

According to another alternative, said gas effluent to be processedcomprises fumes from a fire.

Advantageously, said gas effluent to be processed comprises aerosolsfrom fission products.

Advantageously, said membrane is formed on the basis of ceramic, such assilica carbide, of tungsten or titanium, of KEVLAR® aramid fiber, E. I.du Pont de Nemours and Company (Wilmington, Del. U.S.A.) and/or polymersuch as PEEK (polyetheretherketone) or PTFE (polytetrafluoroethylene).

These features and advantages and other ones of the present inventionwill become more clearly apparent in the following detailed descriptionof several embodiments of the invention, made with reference to theappended drawings, given as non-limiting examples, wherein:

FIG. 1 is a schematic view of a nuclear power plant using a sand filterof the prior art for processing gas effluents,

FIG. 2 is a schematic view of a nuclear power plant applying afiltration method according to an advantageous embodiment,

FIG. 3 is a schematic view of an alternative embodiment of the method,applied continuously on a nuclear power plant, and

FIG. 4 is a schematic cross-sectional view of a membrane according to anadvantageous embodiment.

The method will mainly be described with reference to its application ona nuclear power plant with a containment vessel, however it also appliesto nuclear power plants without any containment vessel, and moregenerally to any type of industrial installation.

As regards pressurized water reactors of the French installed base, thecontainment vessel 100 has a volume of the order of 70,000 to 80,000 m³,and generally consists of a double wall 110, 120 in concrete, asillustrated in FIG. 3. The presence of fission products in thecontainment vessel (in the form of aerosols, vapors and gases) resultingfrom an accident leads to considerable β and γ dose rates in theatmosphere of the containment vessel, and in the sump where the majorityof the aerosols settle. The expected dose rates in both of these phasesare typically of the order of 10 kGy·h⁻¹.

Whatever the case, this value is notably dependent on the degradationcondition of the fuel, on the fission products retained in the primarycircuit, on the distribution of the fission products between theatmosphere and the sump in the containment vessel, itself a function ofthermo-hydraulic conditions prevailing in the containment vessel and ofcourse on the elapsed time since the accident.

The temperature of the gas effluent is typically greater than theambient temperature of the environment outside the power plant. Thegenerally accepted temperature is typically comprised between 40° C. and140° C. according to the scenarios and to the time scale taken intoaccount. It should be noted that temperatures below 40° C. or above 140°C. are possible. As to the humidity rate, it may itself also vary in arange from 0 to 100%, depending on the kinetics and the contemplatedtype of accident.

Radiolysis may lead to the formation of ozone, nitrous oxide N₂O,nitrogen monoxide NO, nitrogen dioxide NO₂, nitrous acid HNO₂ and nitricacid HNO₃.

Various teams have experimentally observed the formation of O₃, of NO₂and of hemipentoxide N₂O₅, in dry air and of O₃, NO₂, HNO₂ and HNO₃ inhumid air (0.5% water mass fraction). To summarize, the radiolyticproducts which may be present in the containment vessel in the case of aserious accident are in majority NO_(x): NO₂ and N₂O, and of course O₃.

Experiments conducted by several laboratories including the IRSSN(<<Institut de Radioprotection et de Sûreté Nucléaire>>) within thescope of programs aiming at controlling the hydrogen risk in nuclearpower plants and notably having dealt with the behavior of catalyticrecombiners, have given the possibility of detecting physico-chemicalreactions generating volatile iodine by dissociation of solid metaliodides.

The table below shows an order of magnitude of the main constituentsestimated for the source term (typical discharge) encountered during aserious accident on reactors of the operating French installed base. Asthe source term is a characteristic of a family of reactors, differencesmay be seen depending on the countries. Nevertheless these values may beused as a dimensioning basis for carrying out the present inventionapplied to a nuclear power plant:

Radiological activity Mass equivalent Noble gases 1E19 Bq About 700 kgOrganic iodine 2E16 Bq About 1 kg Inorganic iodine 1E15 Bq A few gramsCesium 1E16 Bq About 2 kg Strontium 1E15 Bq About 35 g

The significant contribution of the noble gases is to be noted both interms of level of activity and in discharged mass equivalent.

The present method may be dimensioned so as to be able to process flowrates of at least 1 kg/s, advantageously 3.5 kg/s, of humid air broughtto a sufficient driving pressure for operating the system, i.e. at apressure of at least 1 bar, advantageously at least 10 bars absolute,having an average specific gravity of 4 kg/m³ at 5 bars and capable ofprocessing of the order of 1 kg or more of radioactive iodine over aperiod of several months, typically of three months.

In particular, the object of the present method is to providenon-polluting treatment which takes into account the whole of theaforementioned data of a fluid to be processed for which the requiredpurification coefficients are:

-   -   For aerosols, the present method has a purification coefficient        of more than a 1,000.    -   As regards inorganic iodines (I₂), the purification coefficient        is greater than 1,000.    -   As regards organic iodines (ICH₃), the purification coefficient        is greater than 100.    -   The present method advantageously demonstrates a very high        purification coefficient, notably of more than 1,000 on noble        gases.    -   The present method has a purification coefficient greater than        100 on ruthenium tetraoxide (RuO₄).    -   The goal of the present method is also to dilute over time the        activity inside the containment vessel by treating the air        containing radioactive gases.

The mentioned purification coefficient is defined as the measuredupstream/downstream ratio at the filtration device.

The present method uses a membrane filtration method for carrying outdegassing of the containment vessel: releasing as a minimum a flow rateof 3.5 to 7 kg/s under the effect of the pressure prevailing in thecontainment vessel, of a fluid consisting of air, steam, gases of theO₃, NO₂, HNO₂, HNO₃, N₂O₅ type, and of the presence of fission productsin the containment vessel (in the form of aerosols, vapors and gasessuch as noble gases, inorganic iodines and organic iodines).

The present method advantageously uses as a carrier an inert gas such asnitrogen. The fluid treated by the present method may be saturated withwater and with steam. In order to avoid recombinations and the risk ofoxidation of the membranes by the water, either present or not, in thefluid to be treated, the water entirely saturated with gas andpressurized by these gases is directed by a pressure difference towardsseveral, typically four batteries of hydrophobic degassing membranes200. The membrane separation is achieved by sifting, sorption and/ordiffusion. The gases, thus carried away by a carrier gas, such asnitrogen, pass through hydrophobic membranes (a degassing method withhollow fibers), notably by diffusion and separation by osmotic pressure,and are directed towards batteries of selective gas diffusion membranes,210, 220, 230, . . . either in a cascade or in series which allowssorting and selecting of the gases depending on the requirements and/oron the benefit.

The membrane separation methods are based on the selective retentionproperties of membranes towards molecules to be separated. With thefirst gas diffusion membranes in a cascade, it is possible to take intoaccount the whole of the aforementioned data and to recover the whole ofthe noble gases depending on the required purification coefficient.

These are selective membranes, notably based on ceramic, (inert towardsradioactivity), which notably ensure separation of xenon, krypton andargon. The membranes may also be made in other suitable materials, suchas for example carbides, notably of silica, tungsten or titanium,KEVLAR® aramid fiber, E. I. du Pont de Nemours and Company (Wilmington,Del. U.S.A.), polymers, notably PEEK (polyetheretherketone) or PTFE(polytetrafluoroethylene). The whole of the thereby separated gases andpresent in the retentate may be stored in compressed form in sealedreservoirs each comprising a single gas species. These reservoirs allowboth storage, radioactivity decay of fission products, possible re-useof the trapped gases, their neutralization or even their final dischargeby dilution in air.

Gas diffusion and permselectivity of the membranes allow the gases topass over specific ceramic membranes in order to trap inorganic iodineson the one hand and organic iodines on the other hand.

It is also possible to provide a passage over one (or more) membrane(s)on which have been grafted crown calyx4arene molecules trapping targetelements such as cesium, and then on the same principle, passage over amembrane capturing strontium (for example, including another calyxareneselected for its particular affinity for strontium).

Each membrane includes a wall provided with an internal surface and anexternal surface. Said wall having pores P. The wall may be cylindricalor planar. Several walls may be superposed, coaxially in a cylindricalconfiguration or stacked in a planar configuration.

FIG. 4 schematically illustrates more particularly the structure of amembrane 210 with a tubular geometry. The wall of the membrane includespores P suitable for retaining the harmful elements of the gaseffluents. Depending on the material and on the dimensions of the pores,the membrane will be dedicated to the filtration of a given element. Thedimensions of the pores are variable radially, for example decreasingfrom the outside towards the inside, and axially, for example decreasingfrom right to left in the position illustrated in FIG. 4. In thisexample, the gas flow to be filtered flows outside the membrane in thedirection of the arrow A, while the carrier gas flows in the oppositedirection inside the membrane, in the direction of the arrow B. Theelements to be filtered in the gas flow will separate upon crossing thewall of the membrane, from the outside towards the inside, by passingfrom the largest pores to the smallest pores. This separation mayoperate under pressure, by a pressure difference between the inside andthe outside of the membrane wall, or by diffusion.

The membranes are modules with calibrated hollow porous fibers. Byhelically winding the fibers, large exposure to flows with highdegassing rates is possible with a minimum pressure drop. The porediameters are controlled down to a few nanometers at each stage. Thesemembranes thereby include variable porosity along the radial andlongitudinal directions of the membrane surface, adapted to themolecular size to be trapped. An advantageous embodiment in ceramicmaterial further exhibits total harmlessness of the material towardsradioactivity.

The selection of the carrier gas N₂ allows recombination of the gases ofthe NO₂, HNO₂, HNO₃, N₂O₅ type into nitrogen and H₂O. At the outlet ofthe selective membranes, by measuring the gas contamination it ispossible in a first phase to get a clean treated fluid discharge througha controlled solenoid valve towards the cooling and discharge chimney.

This solenoid valve also gives the possibility of sending all or part ofthe recovered nitrogen along a return line 130 for dilution of thecontamination inside the containment vessel. This may be accomplished bysending back an oxygen-rich air but free of any radioactive elementthrough a nitrogen separation membrane.

This method operates without external energy as long as the pressure inthe water conditioning is greater than the lower bound value determinedby the dimensioning of the system, typically 1.5 bars. Manually openingone of the inlet valves of the circuit causes automatic pressurizationof the storage cylinders for storing the carrier gas (generallynitrogen) and the putting of this carrier gas into the circuit via anexpansion valve.

On the other hand in the case of pressure lower than the lower boundvalue, typically 1.5 bars, the gases are degassed from the hydrophobicmembranes by means of an actuator or a pressurized external circuit forexample by means of a vacuum compressor.

Such an embodiment includes a vacuum pump providing suction inside anexchanger provided with an automatic purger and with a booster pumpwhich sends back the water to the conditioning. This vacuum pumpcompresses the sucked-up gases in order to generate the high pressure onthe side of the selective membranes.

The low pressure side of the selective membranes is achieved either bythe suction generated by the air-cooling towers, or by suction of therecycling air inside the containment vessel by the fan.

Advantageously, the method comprises a first front filtration, notablywith a metal pre-filter in order to reduce the outgoing radioactivity, asecond tangential filtration for separating air, CO₂, CO, steam andresidual water from the effluent to be processed, a third filtration bygas diffusion for separating and storing the harmful elements, such asinorganic and organic iodines and noble gases, and discharging theremaining air, CO₂ and CO towards a chimney 150, and a fourth filtrationfor recovering by gas permeation the carrier gas, such as nitrogen, forre-use or dilution inside the containment vessel 100 via a return line130.

With the present method it is also possible to process the radioactiveenvironment of the containment vessel except for an accident, so as toallow faster intervention in the containment vessel during scheduledinterventions. This is notably illustrated in FIG. 3, where theatmosphere contained between both walls 110 and 120 is permanentlymonitored. In the case of a leak in the internal wall 110, thedischarges may thus be filtered continuously until the next maintenanceduring which the leak will be repaired. This avoids stopping the powerplant as soon as such a leak appears.

A particular advantage of the present method is its reliability and itsparticularly high efficiency. Indeed, it is possible to trap more than99.5% of the harmful elements, and it is efficient on noble gases,unlike the existing devices.

The present method uses non-dispersive technology: no risk of foam oremulsion. The filtration systems are robust and without any mobile partsunlike the absorption columns of the rotary type. The method operatesregardless of the changes in pressure of the containment vessel, of thehygrometry rates or of the temperature variation. The method is easy tocreate on an industrial scale, notably by taking into account linearexpansion scales depending on the flow rate. It is clearly moreeconomical than existing devices.

The present method resorts to the modularity principle and uses thetechnologies suitable for this, notably at the connections, assembliesand seals. This modularity allows increased flexibility, the number ofmodules being adjustable depending on the contaminating elements of thecontainment vessel and on their recovery rate to be obtained.

The production of the modules is accomplished by assembling a fewthousand to more than one million of elementary fibers, representing anaccumulated length which may reach 1,000 km, for membrane surfaces ofseveral hundred to several thousand square meters (m²).

The present method comprises modules with hollow fibers with thestructure of a tubular exchanger, with a high pressure (HP) circuit anda low pressure (LP) circuit, a tube side and a calender size. Thepresent invention especially has the advantage of its compactness sincethe specific exchange surface area is much larger than that of a column:2,000 to 3,000 m²/m³ instead of 30 to 300 m²/m³.

The present method allows selective degassing of all radioactive gasesincluding noble gases.

The present method allows full management of gas discharges from thestorage of compressed gases for possible processing or subsequent use bymeans of zeolites in order to transform them into solid waste.

The present method mounted on the ventilation systems allows possibledilution of the contamination of the containment vessel by a system withdouble discharge opportunities.

The present method used for processing gas discharges allows fullmanagement of noble gases.

The present method used for processing the gas effluents from circuitsof nuclear power plants allows full management of their radioactivegases or of those dangerous for the environment.

The present method mounted on the circuits for recovering the evolvedharmful gases during treatments of the injection circuits allows theirrecovery and their processing.

The performance of a membrane separation is the combined result of theintrinsic properties of the membrane:

-   -   selectivity;    -   permeability;    -   operating parameters, such as pressures, temperature, layout of        the flows in the modules.

Another important parameter for a membrane method is the pressuredifference imposed on both sides of the membrane. An increase in thispressure difference (either by increasing the high pressure ordecreasing the low pressure) leads to an increase in the driving forcefor the permeation and makes the separation easier.

For applications related to gas separation, it is often the low pressureof the permeate, the pressure at which the gas is produced, which is theimportant parameter for optimization, the high pressure being generallyimposed by the upstream processes. From the point of view of theseparation performances on a membrane, it is desirable that the lowpressure be as low as possible.

According to another advantageous aspect, the sorting method by means ofa plurality of membranes, as described above for a nuclear power plant,may also be used in other types of industrial installations, and notablychemical plants. The number and the type of membranes will be selectedon the elements to be filtered and to be sorted out.

Although the present invention has been described with reference toparticular embodiments thereof, it is understood that it is not limitedby these embodiments, but that on the contrary one skilled in the artmay provide all useful modifications thereto without departing from thescope of the present invention as defined by the appended claims.

The invention claimed is:
 1. A membrane for filtering gases from anindustrial installation comprising: a plurality of batteries ofselective gas diffusion membranes selective to retain noble gases,organic iodine, inorganic iodine, cesium, strontium, rutheniumtetraoxide, aerosols, vapors, and/or radiolytic products, with eachselective gas diffusion membrane comprising a hydrophobic wall includingan internal surface and an external surface formed of calibrated hollowporous fibers, and pores, in surfaces of the hydrophobic wall, ofvariable dimensions extending between the internal surface and theexternal surface and longitudinally therethrough, wherein each selectivegas diffusion membrane porosity is specific to filter one or more noblegases, organic iodine, inorganic iodine, cesium, strontium, rutheniumtetraoxide, aerosols, vapors, and/or radiolytic products, selecteddepending on installation requirements and/or benefit.
 2. The membraneaccording to claim 1, wherein said hydrophobic wall is cylindrical. 3.The membrane according to claim 1, wherein said hydrophobic wall isplanar.
 4. The membrane according to claim 1, wherein said gases to befiltered flow longitudinally outside said external surface.
 5. Themembrane according to claim 1, wherein the pores increase in size fromsaid external surface to said internal surface.
 6. The membraneaccording to claim 1, wherein pores increase in size longitudinally. 7.The membrane according to claim 1, wherein said gases filtered comprisefumes from an industrial installation after an accident.
 8. The membraneaccording to claim 1, wherein said gases filtered comprise fumes from anindustrial installation during operation.
 9. The membrane according toclaim 1, wherein said gases filtered are extracted from a ventilationsystem.
 10. The membrane according to claim 1, wherein said gasesfiltered comprise fumes from a fire.
 11. The membrane according to claim1, wherein said gases filtered comprises aerosols stemming from fissionproducts.
 12. The membrane according to claim 1, wherein the membrane isformed of ceramic, silica, carbides, tungsten, titanium, aramid fiber,polymers, polyetheretherketone, polytetrafluoroethylene and combinationsthereof.